Evaluation of spatial weighting functions for ex-core detectors by adjoint MCNP calculation
Creators
- 1. Korea Power Engineering Company., Inc., Taejon (Korea, Republic of). Reactor Engineering Group
Description
This paper develops a new approach for the evaluation of spatial weighting functions for ex-core detectors with three dimensional adjoint MCNP calculation. The spatial weighting functions which are independent to core power distribution are widely used in the ex-core detector response analysis. Three dimensional Monte Carlo code, MCNP is used in the evaluation of the spatial weighting functions for ex-core detectors, because it enables the exact geometry modeling of the complex configuration of the reactor and ex-core detector systems without excessive geometry modification or simplification. Multigroup adjoint neutron transport option is applied to improve the calculation efficiency considering relatively large volume difference between the source and the detector regions. The effect of the moderating resin which surrounds the ex-core detector on the spatial weighting function is also analyzed, and it is found that the moderating resin makes the spatial weighting functions sensitive to the source position. (author). 8 refs., 3 figs., 1 tab
Additional details
Additional titles
- Original title (English)
- Anais do 4. Encontro nacional de aplicacoes nucleares. v. 1.
Publishing Information
- Imprint Title
- Proceedings of the 4. Brazilian meeting on nuclear applications. v. 1
- Imprint Pagination
- 646 p.
- Journal Page Range
- p. 604-609.
Conference
- Title
- 4. Brazilian meeting on nuclear applications.
- Original Conference Title
- 4. Encontro nacional de aplicacoes nucleares
- Dates
- 18-22 Aug 1997.
- Place
- Pocos de Caldas, MG (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 28068383
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- MONTE CARLO METHOD; NEUTRON DETECTION; NEUTRON DETECTORS; NEUTRON FLUX; RADIATION DETECTION; RADIATION DETECTORS; REACTOR CORES; REACTOR INSTRUMENTATION
- Descriptors DEC
- CALCULATION METHODS; DETECTION; MEASURING INSTRUMENTS; RADIATION FLUX; REACTOR COMPONENTS
Optional Information
- Notes
- e-mail: jgahn at ns.kopec.co.kr. Imprint:Conference organized jointly with the 11. National meeting on reactor physics and thermohydraulics (11. ENFIR).;Anais do 4. Encontro nacional de aplicacoes nucleares. v. 1.